20 -
23 September 2022
Facility for Rare Isotope Beams at Michigan State University, East Lansing, Michigan (USA)
The 15th workshop on Shielding aspects of Accelerators, Targets, and Irradiation Facilities (SATIF) is tentatively planned to be held in East Lansing, Michigan, USA, on 20-23 September 2022. The SATI...
Published date:
2 November 2021
The expert group was established to develop a nuclear data structure definition that can meet the needs of a broad set of nuclear data users and providers.
Published date:
20 September 2022
The expert group is responsible for managing the activities related to the High Priority Request List (HPRL) for nuclear data, in particular for guaranteeing that the entries are up-to-date and well-...
Published date:
20 September 2022
The event gathered 129 participants from 75 international institutions.
Published date:
6 October 2022
As governments around the world are committing to reaching net zero emissions by 2050, many countries are looking at the role hydrogen can play in mitigating climate change. This page provides more i...
Published date:
16 September 2022
The International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhE) contains reactor physics benchmark specifications that have been derived from experiments that were performed at ...
Published date:
9 November 2022
The primary purpose of the International Criticality Safety Benchmark Evaluation Project (ICSBEP) is to compile critical and subcritical benchmark experiment data into a standardised format that allo...
Published date:
10 November 2022
The International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook contains criticality safety benchmark specifications that have been derived from experiments that were performed at...
Published date:
10 November 2022
The 2021 edition can be downloaded online.
Published date:
22 November 2022
JANIS (Java-based nuclear information software) is an application designed to facilitate the visualisation and manipulation of nuclear data. JANIS will be helpful to engineers and physicists who use ...
Published date:
24 November 2022
MeshTal Viewer user manual
Published date:
25 November 2022
PWR MOX/UO2 Core Transient Benchmark
Published date:
7 December 2022
The 2021 edition contains data from 169 experimental series that were performed at 57 nuclear facilities.
Published date:
13 December 2022
Courses were held in November 2022 in paris, France.
Published date:
14 December 2022
Published date:
17 January 2023
The expert group primarily acted as a forum for scientific and technical information exchange on advanced light water reactor (LWR) fuels with enhanced accident tolerance.
Published date:
18 October 2022
20 -
24 February 2023
NEA headquarters (46, quai Alphonse Le Gallo, 92100 Boulogne-Billancourt, France) with a remote access option
Published date:
30 January 2023
NEA/NSC/R(2020)4
Advanced nuclear fuel cycles to improve the safety, sustainability and economics of nuclear energy are being investigated worldwide. Partitioning and transmutation (P&T) is one of the candidate techn...
Published date:
11 October 2022
NEA/NSC/R(2022)4
Under the auspices of the NEA Nuclear Science Committee (NSC), the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC) was established to co-ordinate scientific activities related to ad...
Published date:
29 November 2022
NEA/NSC/R(2021)1
This benchmark report has been compiled under the guidance of the NEA Working Party on Nuclear Criticality Safety (WPNCS) in the Subgroup on the Role of Integral Experiment Uncertainties and Covarian...
Published date:
30 January 2023
NEA/NSC/R(2021)4
The understanding of nuclear physics and the associated uncertainties is essential to the modelling of all nuclear systems. Nuclear reaction probabilities, emitted particle energies and angles, fissi...
Published date:
8 February 2023
The TAF-ID public version contains only data already published in open literature. Currently, the following systems are available in the public version:
- oxide-carbide fuel (U-Pu-O-C, released Decemb...
Published date:
23 February 2023
View of Dragon Reactor. Photo: AEA Technology.
In 1959, twelve OECD countries began the Dragon Reactor Experiment (DRE) to build a reactor at Winfrith in Dorset, United Kingdom. The Dragon was the fi...
Published date:
14 October 2022
NEA/NSC/R(2019)7
The modelling and simulation of nuclear systems allow scientists and engineers to probe aspects of the operation of these systems beyond what has been precisely measured. This has numerous applicatio...
Published date:
11 October 2022
Under the guidance of the Working Party on Materials Science Issues in Nuclear Fuels and Structural Materials (WPFM), the Expert Group on Fuel Materials (EGFM) focuses on materials science aspects of...
Published date:
3 March 2023
Under the guidance of the Working Party on Materials Science Issues in Nuclear Fuels and Structural Materials (WPFM), the Expert Group on Structural Materials (EGSM) focuses on materials science aspe...
Published date:
3 March 2023
This benchmark is organised to examine the models for fission gas release during anticipated operational occurrences (AOOs).
Published date:
7 March 2023
Under the guidance of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) the expert group performs specific tasks associated with fuel performance aspects of pr...
Published date:
8 March 2023
EGPRS Task Force members met on 3 April 2023.
Published date:
7 April 2023
Development started on DATIF, the DATabase for IFpe, in 2018 in order to enhance accessibility to the IFPE legacy collection of integral fuel performance experiments data, jointly put together by the...
Published date:
12 April 2023
The goal of the Benchmark for Uncertainty Analysis in Best-Estimate Modelling for Design, Operation and Safety Analysis of Light Water Reactors (LWR-UAM) is to determine the uncertainty in light wate...
Published date:
25 April 2023
International experts gathered at the NEA for the commencement of the third phase TAF-ID on 16-17 February 2023.
Published date:
24 February 2023
Thermodynamic databases and accident prevention
Published date:
24 February 2023
Expert groups on structural and fuel materials meet to advance materials science activities
Published date:
24 February 2023
The WPRS met from 20-24 February 2023.
Published date:
17 March 2023
Members of FIDES-II from 12 countries assembled in Prague, Czech Republic, on 17-21 April 2023 for meetings of its Technical Advisory Group and Governing Board.
Published date:
21 April 2023
The Technical Review Groups for both projects met at the NEA headquarters on 3-7 April 2023.
Published date:
24 April 2023
5 -
6 June 2023
Oregon State University, Corvallis, Oregon, United States
Published date:
20 April 2023
NEA/NSC/R(2021)5
Since the early 2000s there is an increasing demand from nuclear research, industry, safety and regulation for best-estimate predictions to be provided with their confidence bounds. Consequently, an ...
Published date:
18 April 2023
NEA/NSC/R(2021)3
Monte Carlo criticality calculations involve a two-step procedure based on a stochastic implementation of the power iteration method: first, achieve convergence of the fission source distribution dur...
Published date:
17 February 2023
NEA/NSC/R(2022)5
This report presents the results of a benchmark study on innovative fuels for fast reactors using fuel performance codes. Irradiation results were shared among participants of the expert group and co...
Published date:
3 April 2023
22 -
26 May 2023
Zanhotel Europa, Via Cesare Boldini 11, Bologna, Italy + virtual option on ZOOM
Published date:
17 May 2023
Under the guidance of the Nuclear Science Committee (NSC), the Working Party on Materials Science Issues in Nuclear Fuels and Structural Materials (WPFM) addresses materials science aspects of nuclea...
Published date:
1 June 2023
Lead-cooled Fast Reactors (LFR) are rather new concepts which have gathered increasing international attention after the Generation-IV International Forum (GIF) selected them as promising candidates ...
Published date:
9 June 2023
The FIDES-II framework is designed to do more than just produce data on transient fuel behavior and safety related issues.
Published date:
13 June 2023
WPFM held meetings on 23-25 May 2023.
Published date:
13 June 2023
The first International School on Simulation of Nuclear Reactor Systems (SINUS) took place on 22-23 May 2023.
Published date:
14 June 2023
Kick-off workshop of the thermal hydraulic code validation benchmark for high temperature gas-cooled reactors using High Temperature Test Facility (HTTF) data.
Published date:
16 June 2023
10-year FIDES-II strategic plan will define key research needs in a variety of technical disciplines.
Published date:
19 June 2023
The annual WPRS Benchmarks Workshops took place on 22-26 May 2023 in Bologna, Italy.
Published date:
13 June 2023